ML20155J298

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Inservice Insp Summary Rept
ML20155J298
Person / Time
Site: Quad Cities Constellation icon.png
Issue date: 05/07/1986
From:
COMMONWEALTH EDISON CO.
To:
Shared Package
ML20155J289 List:
References
NUDOCS 8605230085
Download: ML20155J298 (13)
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ISI

SUMMARY

REPORT May 7, 1986 COMMONWEALTH EDISOf4 P.O. Box 767 Chicago, Illinois 60690 QUAD CITIES NUCLEAR POWER STATION 22710 206 Avenue North Cordova, Illinois 61242 O UNIT i Commercial operating data: February 18, 1973 i

8605230085 860513 PDR ADOCK 05000254 G PDR 0506H/0216Z

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r INTRODUCTION General Electric (GE) was contracted by the Commonwealth Edison Company (CECO) to perform the second Inservice Inspection (ISI) of the second inspection f)

v interval on Unit 1 of the Quad-Cities Nuclear Power Station. The scope of GE activities included the performance of Liquid Penetrant, Magnetic Particle, and Ultrasonic Nondestructive Examinations. Visual examinations were performed by certified CECO inspectors. The examinations were performed on portions of the reactor pressure vessel and its associated coolant systems and components.

The Nondestructive Examinations were performed according to the requirements of the Quad-Cities Nuclear Power Station Units 1 and 2 Inspection and Testing Program which complies with Section XI of the ASME Boller and Pressure Vessel Code, 1980 Edition through 1980 Winter Addenda.

This report compiles the information pertaining to the Nondestructive Examinations conducted by GE and Visual Examinations performed by CECO. It is divided into Discussion and Data sections.

The Discussion section addresses the scope, scheduling, and performance of NDE activities, personnel, calibration and examination report generation, and the methods used to interpret and evaluate the Nondestructive examination results.

The Data section contains tabular listings of GE's equipment and personnel rosters (table II and III), procedures used (table IV) and summarized results of all ISI examinations (table I).

DISCUSSION Scope of GE Activities Nondestructive Examinations were performed on portions of the Reactor Pressure Vessel and its associated coolant system piping and components as directed by Quad-Cities personnel. The examinations were performed to raeet the requirements of the Quad-Cities Nuclear Power Station, Units 1 and 2 inspection and testing program. The procedures used were prepared and approved by Commonwealth Edison, and comply with the requirements of Section XI of the ASME 1980 Edition through 1980 Winter Addenda.

Scheduling and Performance The daily schedule of examinations activities was governed by the preparation and availability of the items to be examined, and the anticipated personnel exposure within the work area. The Inservice Inspection Schedule was designed to located and correct detrimental conditions as early in the outage as possible, to minimize conflict with Critical Path Activities.

Ultrasonic examinations were generally performed by teams of two or more individuals. Liquid Penetrant, Magnetic Particle, and Visual Examinations were conducted by single individuals, or teams consisting of an examiner and an assistant or helper.

0506H/0216Z Personnel Personnel participating in the examination activities are certified in

( accordance with SNT-TC-1A 1975/1980 Edition. They are identified by name, level of certification, and function, on the report appropriate to each item examined. Table III listed GE's personnel, their levels of certification, and job function. Certification records of all participating personnel are on files at Quad-Cities Station.

Calibration and Examination Report Generation Prior to the start of an ultrasonic examination series, a system calibration was performed on the calibration block appropriate to the item to be examined. An ultrasonic calibration report was prepared, identifying the personnel, equipment, and materials, and used as an aid in the interpretation and evaluation of examination results. Each calibration report is uniquely identified by a number, and references the applicable examinations by examination report number and item identification.

An examination report, appropriate to the NDE method, was prepared for each examination. The examination reports identify the item examined, the procedure used, the examination results, and references the appropriate calibration report by number.

Interpretation and Evaluation The interpretation and evaluation of examination results were based on the location, shape, and apparent dimensions of the indication. Additional f-~

information obtained from other sources, such as radiography or ultrasonic

(_) thickness measurements, was used in the. interpretation and evaluation process as circumstances and availability indicated. The ultrasonic examinations were performed with the manual, master / slave, and automated ultrasonic systems.

The automated ultrasonic examinations were performed with the Ultra Image III computerized data acquisition system utilizing a VCR ALARA-1 automated scanner. The digitized data is permanently stored on floppy discs and the "A" scan is recorded on VHS format video tapes for later retrieval analysis and display. The master / slave data was manually recorded and the A scan was recorded by VHS format video tape. Recording reporting levels, and acceptance criteria are as detailed in the examination procedures.

The results of all I.S.I.'s examinations are summarized in table I.

O 0506H/0216Z .

QUAD-CITIES UNIT ONE OP CYC 08 m

U SUMMARIZED ISI RESULTS TABLE I Exam Report No. Component / Weld No. Method Remarks RA-001 02L-F6*(l) UT-45' ID Geom.

RA-002 02H-F6*(l) UT-45' ID notse RA-006,R036 R036A 10S-F8*(l) UT-0*, 45' NRI R003,R007 10BD-S17*(l) UT-0*, 45* ID Geom.

R004, R008 10AD-S15*(l) UT-0*, 45' NRI R005, R009 1404_4*(2) PT Accept.

R010, R011 3950-M-313.1(3) VT-3,4 No Ind R012 3950-M-312(3) VT-3 No Ind R013 1001-29A Viv Bolting (I) VT-1 No Ind R017, R018 10AD-S8*(l) UT-0*, 45' ID(Root) Geom R027 02AS-S4*(4) UT-0*, 45' ID & OD Geom R035, R038 02A-S7*(l) UT-0*, 45' NRI R039 02AS-S4*(l) PT Accept R040 10S-F8*(l) PT Accept R041 02BD-S2*(I) -PT Accept R042, R050 02BD-S2*(l) UT-0*, 45' Root Geom.

- bm, R059 12S-F4R*(I) PT Accept R060 10HS-F10A*(l) PT Accept R061, R229 1012A-W-104(1) PT Accept R063, R064 10HS-F10A*(l) UT-0*, 45' OD Geom.

R065 N8A-Fl*(l) UT-45' NRI R066 12S-F4R*(l) UT-45' OD Geom.

R070 N8A-Fl*(l) PT Accept R072 14A-S48R*(l) UT-45' 00 Geom.

R075 14A-S48R*(l) MT Accept R077 13S-S1*(l) MT Accept R078 30A-S12*(l) MT Accept R079 30A-S13*(l) MT Accept R080 30A-S14*(l) MT Accept R081 30A-S15*(I) MT Accept R082 30A-S16*(l) MT Accept R083 30A-S21*(l) MT Accept R084 02K-Fl*(I) UT-45' NRI R095 02J-Fl*(l) UT-45' ID & 00 Geom.

R100 02J-Fl*(l) PT Accept R101 30A-S13*(I) UT-0*, 45' NRI R102 30A-S16*(I) UT-0*, 45' NRI R103 30A-S14*(l) UT-0*, 45' NRI R104 30A-S12*(l) UT-0*, 45* 10 Geom.

R105 30A-515*(I) UT-0*, 45' NRI R107 "B" Recirc Pump Studs (l) UT-0* NRI O

0506H/0216Z -

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Exam Report No. Component / Held No. Method Remarks R110 220-57A V1v Bolting (l) VT-1 Accept R111 220-58A V1v Bolting (l) VT-1 Accept Ril2 1402-6A Viv Bolting (I) VT-1 Accept R113 1402-9A Viv Bolting (I) VT-1 Accept R114 3967-M-323.I(3) VT-3 No Ind R115 3967-M-323(3) VT-3 No Ind R116 3967-M-322(3) VT-3 No Ind R117 3967-M-321(3) VT-3 No Ind R118 3967-M-320(3) VT-3 No Ind R119 3967-M-319(3) VT-3 No Ind R120 3967-M-318(3) VT-3 No Ind R121 3967-M-317(3) VT-3 No Ind R122 3967-M-316(3) VT-3 No Ind R123 3001A-M-105(1) VT-3 Accept R124, R126 30018-M-102 A & B(I) VT-3, 4 No Ind R125, R138 30018-W-103(1) VT-3, 4 Accepted R127 10AD-S8*(l) PT Accept R128 02K-Fl*(l) PT Accept R129, R130, R131 N2B Nozzle-Vessel *(l)' UT-0*, 45*, 60* NAD R132 1003A-1*(2) UT-0*, 45* ID Geom.

R133, R145, R146 N8A Nozzle-Vessel *(l) UT-0*, 45*, 60* NAD R134 03-F9*(I) PT Accept R135 03-F10*(I) MT Accept R136, R175 0308-W-101(I) VT-3, 4 No Ind R137, R184 1403-H-102(1) VT-3, 4 Accept n

Accept U R140 R141, R152, R157 Rx Head Flange *(l)

Rx Head-Dollars Weld *(I)

MT UT-0*, 45*, 60* NAD R142 Rx Head-0* Merid*(I) UT-0* NAD R143 Rx Head-180* Merid*(I) UT-0* Spot Ind **

R144, R153, R156 Rx Head Flange *CI) UT-0*, 45*, 60* NAD R147, R163, R170 RPV 339' Vert. Seam *II) UT-0*, 45' NAD R148, R162, R169 RPV 99* Vert. Seam *(l) UT-0*, 45*, 60* ID Clad Roll R149, R166 N3A Nozzle-Vessel *CI) UT-0*, 60* ID Clad Roll R150 N8A Nozzle-Vessel *(I) UT-IRS Geom. reflect R151, R167, R168 UT-0*, 60*, 45' NAD RPV-SheeltoFlange*(I) UT-45*, 60* ID' clad ripple R154, R158 Rx Head-0* Merid* I)

RISS, R159 Rx Head-180* Merid*(l) UT-45*, 60* ID Clad ripple R160 03-FIO*(l) UT-0*, 45' NRI R161 03-F9*(l) UT-0*, 45* NRI R164 32A-F13*(l) MT Accept R165 N3A Nozzle-vessel *(I) UT-IRS NRI R171 W3A Nozzle-vessel *(I) UT-45' NRI R172 N4A Nozzle-vessel *(l) UT-0* Spot Ind **

R173, R174 N4A Nozzle-vessel *(I) UT-60*, 45' NAD R176, R177, R214 0200-W-il7 A & B(I) VT-3, 4 Accepted R178, R179, R180 3204F-W-101 A & BCl) VT-3, 4 No Ind R181, R182, R183 3204E-H-101 A & B(I} VT-3, 4 No Ind R185, R218, R249 1403-H-103 A & B(1) VT-3, 4 No Ind R186 10438-M-301.2(3) VT-3 No Ind R187 203-3A Viv Body (l) VT-1 Accepted A

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0506H/0216Z . _ _ _ _ _ _ _

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Exam Report No. Component / Weld No. Method Remarks t ).

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R188 1001-68A Viv Biting (I) VT-1 Accepted R189 1001-33A Viv Biting (l) VT-1 Accepted R190, R191 1008A-N-20l(I) VT-3, 4 No Ind R192, R193 1008A-M-203 A & B(1) VT-3, 4 No Ind R194-R196, R298-R300 CR0 Housing FLNG Biting (l) VT-1 Accepted R198 32A-F13*(l) UT-0*, 45* ID Root Geom.

R199 32A-S5*(l) UT-45* ID Root Geom.

R200 2305-1*(2) UT-0*, 45' ID Root Geom.

R201 2305-2*(2) UT-0*, 45* ID Root Geom.

R202 1012A-10*(2) MT Accept R203 1012A-10*(2) UT-0*, 45* I0-00 Geom.

R204 23S-57*(l) HT Accept R205 RPV-vessel skirt *(l) MT Accept R206 32A-F16*(I) MT Accept R207 235-S7*(I) UT-0*, 45' ID-00 Geom.

R208 32A-F16*(l) UT-0*, 45' ID-0D Geom.

R209, R210 1025-M-102(l) VT-3, 4 No Ind R211-R213, R281 0200-H-Il3 A & B(1) VT-3, 4 No Ind R215, R216 30018-M-101.2(l) VT-3, 4 No Ind R217, R295 30018-M-101.I(I) VT-3, 4 Accepted R219 02A-S7*(I) PT Accept R220 2305-l*(2) MT Accept R221 2305-2*(2) MT Accept rm R222 1009A-6*(2) MT Accept d R223 1009A_4*(2) MT Accept Accept R224 1006A-88*(2) MT R225 1009A-1*(2) MT Accept '

R226 1008A-13.1A*(2) MT Accept R227 02H-F6*(l) PT Accept R228 02L-F6*(l) PT Accept R229 1012A-N-105*(I) PT Accept R230 N2C-Nozzle-vessel *(l) UT-IRS NRI R231 N28-Nozzle-vessel *CI) UT-IRS NRI R232, R233, R234 N2C-Nozzle-vessel *(I) UT-0*, 45*, 60* NAD R235 (l) VT-1 Accepted 220-628 Viv Body *CI) Accepted R236 203-2A Viv Body

  • VT-1 R237 3953-M-310(3) VT-3 No Ind R238 3953-M-312(3) VT-3 No Ind R239 3953-M-314(3) VT-3 No Ind R240 3953-M-315(3) VT-3 No Ind R241 3953-M-316(3) VT-3 No Ind R242 3953-M-317(3) VT-3 No Ind R243 3953-M-317.l(3) VT-3 No Ind R244 3967-M-324(3) VT-3 No Ind R245 3967A-M-301(3) VT-3 Accepted R246, R247 0200-M-110(1) VT-3, 4 No Ind R248 RPV Internals *(l) VT-1, UT Accepted R250 2304-M-203(2) VT-3 No Ind R251 2304-M-204(2) VT-3 Accepted 0506H/0216Z Exam Report No. Component / Weld No. Method Remarks f')

V R252 2304-W-201(2) VT-3 Accepted R253 2304-M-205(2) VT-3 Accepted R254 32048-M-201(2) VT-3 No Ind R255, R297 2307-W-207(2) VT-3, 4 Accepted R256 1052-M-303(3) VT-3 Accepted 1 R257 1002-M-303(3) VT-3 No Ind R258 1003A-W-304(3) VT-3 No Ind R259 1005A-N-302.7(3) VT-3 No Ind R260 1005A-N-302.6(3) VT-3 No Ind R261 1005A-M-302.2(3) VT-3 No Ind R262 1005A-M-302.1(3) VT-3 No Ind R263 3950-M-310(3) VT-3 No Ind R264 3450-M-309(3) VT-3 No Ind R265 3950-W-308(3) VT-3 Nc Ind R266 3967-M-312.1(3) VT-3 No Ind R270, R271 0200-M-ll2(I) VT-3, 4 Accepted R272, R273 0220-M-lll(I) VT-3, 4 Accepted R274 220-588 Viv Body (I) VT-1 Accepted R275 220-62A Boltingil) VT-1 Accepted R276 1005A-M-301.7(1) VT-3 Accepted R277 0200-H-114(I) VT-3 No Ind R278 0318A-N-201(2) VT-3 Accepted R279, R280 1012A-N-104(1) VT-3, 4 Accepted R282, R283 1202-M-104(l) VT-3, 4 No Ind o R285 3958-M-301(3) VT-3 No Ind

(,) R286 1010-M-202.l(2) VT-3 No Ind R287, R288 1008A-M-202(2) VT-3, 4 No Ind R290 1402-25A Bolting (l) VT-1 Accepted R291, R292 0200-W-119 A & B(l) VT-3, 4 No Ind R293, R294 1012A-N-102(l) VT-3, 4 Accepted R296 3950-M-314(3) VT-3 No Ind

  • Weld Number ID (I)IWB (2)IWC Cl)IND Note: IWF supports will fall under IWB, IWC, or IND category.
    • No interference with angle exams - accepted Terms Accept - satisfactory condition ID Geom. - Inner diameter geometry OD Geom. - Outer diameter geometry NRI - No Recordabel Indication NAD - No Apparent Defects No Ind - No Indications 0506H/0216Z QUAD-CITIES UNIT 1 INSERVICE INSPECTION GE'S EQUIPMENT ROSTER t i

'~ ' TABLE II ULTRASONIC INSTRUMENTS Description Manufacturer Model Serial No.

Automatic UT #1 Ultra image inter. UI III 101368401 201358401 301368401 401358401 Scope SONIC MARK I Sonic Mark I 732203 Scope Kraut Kramer CL 202 801203 Scope Kraut Krmer USL 32 26680-522 Scope Kraut Kramer USL 32 26680-521 Scope Kraut Kramer USL 38 211830 SEARCH UNITS

' Description Manufacturer Model Serial No.

Search Unit KB-Aero tech WSY-70-2 2.0 MHZ A06666

<- Search Unit KS-Aerotech WSY-70-2 2.0 MHZ A06668

(_)) Search Unit KB-Aerotech .375" x 5.0 MHZ A28031 TRCr 2 Aust-2.0MHZ 85-99 Search Unit 516MA Search Unit SWRI SLIC-40 067 Search Unit KB-Aerotech 28mm x 13mm-2.0MHZ 028494 Search Unit Gamma .375 x 5.0 MHZ B07512 Search Unit Gamma .50 x 2.25 MHZ KB2730 NOTE: Additional search units supplied by Commonwealth Edison O

0506H/0216Z REFERENCE BLOCKS Description Manufacturer Model Serial No.

{~ }

Ref. Block, SS GE ROMPAS 795398 Ref. Block, SS GE ROMPAS 795370 Ref. Block, SS GE ROMPAS 795371 Ref. Block, SS GE ROMPAS 795373 Ref. Block, 1" SS GE IIH TS-1221

-SURFACE EQUIPMENT Description Manufacturer Model Serial No.

Magentic Yoke Parker Research B-30 1203 o

l O 0506H/0216Z . ._ _,

QUAD-CITIES UNIT INSERVICE INSPECTION ISI PERSONNEL i ,-)

TABLE III The following General Electric personnel participated in the inspection as Indicated:

NAME MT PT UT IGSCC** OVERLAY ** FUNCTION Alcantara, Ed II II Examiner Aker, Virgil II II I

  • Ast. Examiner Armes, Walter I-S NDE Helper Bendele, Ronald II II II II Examiner Carlin, William II II II Examiner DuBose, George II II II II II Examiner Dummer, Brad III III III II Supervisor Edgel, Doug II II II II Examiner Evich, Mark I I I
  • Ast. Examiner Hart, Randy II II II Examiner Lancaster, Jack I NDE Helper Nash, Patrick II II II II Examiner O'Connor, Timothy NDE Helper Parr, Ronald I II II II Examiner Pietzak, Rick III III Supervisor Plotz, Craig I-S NDE Helper

/) Reczek, Edward III III Supervisor

\~/ Russel, Dennis II II I

  • Ast. Examiner Sells, Daniel II II II NDE Helper Trotter, Edward II II II Ast. Examiner Horby, Mike I NDE Helper
  • Level I IGSCC Training for Master / Slave UT System
    • EPRI qualified on or after Sept. 10, 1985

<~T 0506H/0216Z __

. .s TABLE III (cont'd)

The following CECO personnel participated in the inspection as indicated:

NAME VT-1 VT-2 VT-3 VT-4 FUNCTION Castro, Robert II II II Examiner Crippes, Thomas II Examiner Digrindakasis, Nick P. II Examiner Do, Hien Q. .

III Examiner Ficming, Kevin M. II Examiner Ford, James R. II QC Lead Examiner Huizenga, Dave II Examiner Knapp, Gary E. II II II II Examiner

Koenes, John E. II Examiner Medulan, Kenneth K. II II II II Lead Examiner Phippen, Robert II Examiner Sack .Chris II Examiner Schmidt, Albert J. II Examiner Steiner, Mike II Examiner Tucker, Roger II Examiner Wagner, Bernard II II II II Examiner O

0506H/0216Z QUAD-CITIES UNIT 2 INSERVICE INSPECTION NDE PROCEDURES TABLE IV PROCEDURE REV. DESCRIPTION NDT-B-1 2 Magnetic Particle Examination for ASME Section XI Class IWB and IWC Components for Nuclear Stations.

NDT-C-2 15 Preservice and Inservice Ultrasonic Inspection of Similar and Dissimilar Metal Pipe Welds at Nuclear Stations.

NDT-C-10 10 Ultrasonic Inspection of the Inner Radius of the Nozzle-to-Vessel Junction at Nuclear Stations.

NDT-C-14 8 Ultrasonic Inspection of Pressure Retaining Bolting two inches or greater in diameter at Nuclear Stations.

NDT-C-27 2 Ultrasonic Inspection of DE-CLAD Feedwater Nozzle Inner BORE and RADIUS OF BOILER WATER REACTORS.

NDT-C-30-80 0 Ultrasonic Examination of Reactor Vessel Welds to NRC Reg. Guide 1.150 for Bolling Water Reactors.

() NDT-C-31-80 0 Beam Spread and Refracted Angle Determination to NRC Reg. Guide 1.150 for Bolling Water Reactors.

NDT-C-37 0 Ultrasonic Examination of weld overlay repaired pipe weld joints.

NDT-D-2-80 5 Non-Aqueous Red Dye Liquid Penetrant Examination for Section XI class IWB and IWC components for Nuclear Stations.

VT-1-1 2 Visual examination - welds, pressure retaining bolting, and component internals.

VT-2-1 1 Visual examination - system hydrostatic and leak tests.

VT-3-1 1 Visual examination - component supports.

VT-4-1 1 Visual examination - snubbers, shock absorbers, spring and constant load type supports.

V 0506H/0216Z l F3RM NIS.1 CWNERS' CATA REPOST FE3 INSEQVICE INSPECTIONS As required by tbs Provisions of the ASME Code Celes Connonwealth Edison, P.O. Box 767, Chicago, Illinois 60690 O g, o ,,,,

(Namne and Address of Owest) 2, Maas Quad Cities Nuclear Power Station, 22710 206th Ave North, Cordova, IL 61242 (Nanne and Address of Maat)

3. Plant Unit _One 4. Owner Certifieses of Authermr== (if required) N/A S. Casaniercial Service Date 2-18-73 6. National Board Number for Unit NA
7. C:- ;:-- es ! :;::i.4 Manufacturer

 ; - - - et Manufacturer or Installer 5 tate of National Apportenesee or Install ** Serial No. Province No. Board No.

Reactor Press, Vennel 1 Babcoci: & Wilcox $10-0122-51-52 B0074093 NA 1

Recirculation Dravc, Corporation NA NA NA 1,2 CRD Grinnell NA la NA 1, 2, 3 A-UOl93224 RHRS Southwest Res./Grinnell NA B-UO193225

  • NA 1

RUCU Grinnell/ Mechanical Inc. NA NA NA 1, 2 Core Spray Grinnell/liechanical Inc. NA NA NA 1, z HPCI Grinnell NA NA Im 1

!!ain Steam Grinnell NA NA IM L

Feedwater Grinnell NA NA NA viesal uen. 3 Cooling Utr. NA NA NA Grinnell

  • Heat Exchangers Only Note: Supplemental sheets in form of lists. sketches, or drawings may be used provided (1) size is 8% in. x 1I in..

(2) ;nformation in items 1 through 6 on this data report is included on each sheet, and ( 3) each sheet is numbered tr.d the number of sheets is recorded at the top of this form.

This form (E00029) may be obtained from the Order Dept., ASME. 345 L 47th St., New York, N.Y. 10017

FORM NIS4 (back)

3. am age asso pense 1-14-86 c. 3-28-86 9. Inspection laterval fress 2- 18-86 to 2-18-93
10. Abstreet of'E=h lastede a list of-- " ":x and a statement concerning sessus of work requimd for cumet ineerval. See Note (1) Below 1I. Abstract of Conditions Nond #o Defects Were Found Per ISI ASME XI Schedule
12. Abstract of Correcem Meassees Recommended and Taken NA We certify that the statements made in this report are correct and the examinations and correctm mee-sures takes conforne to the rules of the ASME Code,Section XI.

Dew MN 7 ns L(e sign.d CwinwwekA Pdhmy A dbu I

Owner Certificate of Authorisation No. (if applicable) NA Expiration Date A/d S CERTIFICATE OF INSERVICE INSPECTION I, the ui '; :f, holding a valid comen issued by the National Board of Boder sad Pressure Vessel Inspectors and/or the $tsee or Province EM and employed by %CE d4 n r6 of eL vL l /l - have inspected the components described in this Owners' Dat/ Report dunng the period

' M 'AV- Pr' co a:r - #4% and state that to the best of my knowledge and belief, the Owner has performed examinaticas and taken correctm measurer described in this owners

  • Data Report in accordance with the sequirements of the ASME Code, Secoon X'.

By signing this certificate neither the Inspector not his employer makes any warranty, expmseed or implied.

l concerning the examinations and correctm measures described in this Owners' Data Report. Furthermore, j neither the Inspector nor his employer shall be liable in any manner for any personalinjury or property damage or a loss of any kind anamg from or connected with this inspection.

Date Ab # 19 Md

- -[ e. Commissions 8 A MM IR 630 National Board. State. Province and No.

/ Inspector's Signature (1) Approximately 34% of the required inspections on ISI class 1, 2, 3 were completed for the first period of the second 10 year inspection interval (approximately 17% for this outage). Refer to attached table I for operation cycle 8 list of examinations. Additional ISI class 1 stainless steel welds were examined . _ _

ultrasonically per NRC's requirements. A leakage test was performed on the Reactor pressure vessel and on the recirculation system at the end of the refuel outage.

O J

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